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CORRESPONDENCE-LETTERS, NRC TO UTILITY  and OUTGOING CORRESPONDENCE

Nickel +, Copper +, Nitrogen +, Hydrogen +  and Lead +

10 CFR 50 +  and 10 CFR 50.35 +

NRC 245 +  and NL 80468 +

05000255  +  and 00255  +

Lainas G +  and Office of Nuclear Reactor Regulation +

ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +, ML18047A316 +  and ML18047A316 +

NUREG-0690 +, NUREG/CR-2083, Forwards NUREG/CR-2083, Evaluation of Threat to PWR Vessel Integrity Posed by Pressurized Thermal Shock Events. Joint Ofc of Nuclear Reactor Regulation/Ofc of Research Team Will Review Rept.W/O Encl +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0649, Summary of ACRS Subcommittee on Auxiliary Sys 880810 Meeting in Washington,Dc to Discuss Proposed Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Related Info, Including List of Submitted Documents Encl +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +  and NUREG-0224, Safety Evaluation Accepting Adequacy of Low Temp Overpressure Mitigating Sys Per Multi-Plant Action Item B-04,NUREG-0224 & GDC 15 & 31 +

Illinois +, Maryland +, Washington +, California +, Virginia +, Idaho +, Michigan +  and New Mexico +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Shutdown Cooling +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +  and Decay Heat Removal +

Vandewalle D +  and Consumers Energy +

Generic Issues Program +  and Control of Heavy Loads +